A review of microstructural features in fast reactor mixed oxide fuels
Source abstract
Abstract
Abstract As an alternative to traditional uranium dioxide (UO2) fuels, mixed oxide (MOX) fuels were developed to dispose of industrial and military stores of plutonium (Pu) through the incorporation of plutonium dioxide (PuO2) powder into a UO2 base fuel. The high temperature and chemical stability characteristic of oxide fuels would be maintained, while the added Pu would ultimately be eliminated from long term storage. Plutonium could be extracted from spent light water reactor (LWR) fuels, acting as an additional step to close the fuel cycle and mitigate potential environmental or proliferation concerns. This review summarizes the primary features associated with fast reactor MOX fuels, including fuel restructuring, actinide redistribution, solid fission products, plutonium agglomerates, joint oxide gain, and fuel-cladding chemical interaction. A summary of research efforts within the last 10 years and directions for future research are discussed.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
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